ML17331B305

Monthly Operating Rept for Feb 1994 for DCP Unit 2

ML17331B305
Person / Time
Site:	Cook
Issue date:	02/28/1994
From:	Blind A, Janisse J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9403180080
Download: ML17331B305 (9)

Text

ACCELERATED DIS UTION DEMONSTPA.TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9403180080 DOC.DATE: ~i~~

NOTARIZED: NO DOCKET g

FACIL:50-316 Donald C.

Cook Nuclear Power Plant, Unit 2, Indiana M

05000316 AUTH.NAME AUTHOR AFFILIATION JANISSE,J.D.

Indiana Michigan Power Co.

(fdrmerly Indiana 6 Michigan Ele BLIND,A.A.

Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP,NAME RECIPIENT AFFILIATION R

SUBJECT:

Mo thl operating rept for Feb 1994 for DCP Unit 2.

W 940307 ltr.

DISTRIBUTION CODE:

IE24D COPIES RECEIVED:LTR ENCL Q SIZE: 5 TITLE: Monthly Operating Report (per Tech Specs)

NOTES:

D RECIPIENT ID CODE/NAME PD3-1 PD INTERNAL: AEOD/DOA N

4DQRS OEAB EG FI 01 EXTERNAL EGE(G BRYCE E J

~ H NSIC COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME HICKMAN,J AEOD/DSP/TPAB NRR/DRIL/RPEB RGN3 NRC PDR COPIES LTTR ENCL 1

1 1

1 1

1 1

1 A

D D

D NOTE TO ALL"RIDS" RECIPIENTS:

D D

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR

'11 ENCL 11

Indiana Michigan~

Power Company Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901 IN!NANSl PvHCimliGQM llaOWM March 7, 1994 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 Gentlemen:

Pursuant to the requirements of Donald C.

Cook Nuclear Plant Unit 2 Technical Specification 6.9.1.10, the attached Monthly Operating Report for the month of February 1994 is submitted.

Respectfully, a.da.~

A.A. Blind Plant Manager Attachment c'RC Region III D.R. Hahn R.C. Callen S.

Hamming Z.G. Keppler INPO Records Center ANI Nuclear Engineering Department E.E. Fitzpatrick R.L.

Simms W.G. Smith, Jr.

S.J.

Brewer D.W. Paul S.H. Steinhart J.L. Leichner J.A.

Isom D.G. Turner E.A. Smarrella J.C. Krieger D.F. Krause M.E. Russo

,9403180080 940228.

~PDR,<~'DOCK 050003lb I

"IPDR='M

N.R.C.

OPERATING DATA REPORT DOCKET NO.

DATE COMPLETED BY TELEPHONE OPERATING STATUS

l. Unit Name D.

C.

Cook Unit 2

2. Reporting Period FEB 94

3. Licensed Thermal Power (MWt) 3411 4.

Name Plate Rating~ (Gro'ss MWe) 1133

5. Design Electrical Rating (Net MWe) 1090 6.

Maximum Dependable Capacity (GROSS MWe) 1100 7.

Maximum Dependable Capacity (Net MWe) 1060

,2,'5 0-3 16 02/Mar/94 JD Janisse 616-465-5901 notes

8. If Changes Occur in Capacity Ratings (Items no.

3 through

7) Since Last Report Give Reasons 9.

Power Level To Which Restricted. If Any (Net MWe) 10.

Reasons For Restrictions. If Any:

11.

Hours in Reporting Period 12.

No. of Hrs. Reactor Was Critical

13. Reactor Reserve Shutdown Hours 14.

Hours Generator on Line

15. Unit Reserve Shutdown Hours l6. Gross Therm.

Energy Gen.

(MWH) 17.

Gross Elect.

Energy Gen.

(MWH)

18. Net Elect.

Energy Gen.

(MWH)

19. Unit Service Factor

20. Unit Availability Factor

21. Unit Capacity Factor (MDC Net)

22. Unit Capacity Factor (DER Net)

23. Unit Forced Outage Rate 24.

Shutdowns Scheduled over Next Six Refuelin out of 70 da s.

This Mo.

Yr. to Date 672.0 1416.0 494.2 1136.0 0.0 0.0 494.2 1116.9 0.0 0.0 1099769 2846763 343460 904970 326728 866986 73.5 78.9 73.5 78.9 45.9 57.8 44 '

56.2 3.5 11 '

Months (Type, Date,and Cumm.

141672.0 95985.0 0.0 92892.8 0.0 284960858 92512870 89092968 66.7 66.7 60.2 58.7 15.3 Duration):

25. If Shut Down At End of Report Period, Estimated Date of Startup:

March 2, 1994

26. Units in Test Status (Prior to Commercial Operation):

Forcast INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Achieved

AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO.

50-316 UNIT TWO 02/Mar/94 02/Mar/94 JD Janisse JD Janisse

• TELEPHONE 616-465-5901 DAY 02/01/94 02/02/94 02/03/94 02/04/94 02/05/94 02/06/94 02/07/94 02/08/94 02/09/94 02/10/94 02/11/94 02/12/94 02/13/94 02/14/94 02/15/94 02/16/94 FEB 94 AVERAGE DAILY POWER LEVEL 839 957 960 909 553 574 597 600 601 601 602 603 605 608 608 608 FEB 94 DAY 02/17/94 02/18/94 02/19/94 02/20/94 02/21/94 02/22/94 02/23/94 02/24/94 02/25/94 02/26/94 02/27/94 02/28/94 AVERAGE DAILY POWER LEVEL 608 608 608 606 359 0

0 0

0 0

0 0

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: FEBRUARY 1994 UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

PAGE 1 OF' D

C.

COOK UNIT 2 March 7, 1994 R. D. Reynnells (616) 465-5901 DURATION NO DATE TYPES'OURS METHOD OF SHUTTING DOWN REASON~

REACTOR~

LICENSEE EVENT REPORT NO SYSTEM CODE'OMPONENT CODEs CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE 234 940221 F

177.8 H

94-01/U-2 SB ISV At 1413 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.376465e-4 months <br /> on 940221 the reactor tripped on a LoLo level ~

signal on g4 Steam Generator.

This signal was the result of the P4 S/G Stop Valve closing when the g4 Stop Valve Dump Valve opened during post maintenance testing.

The cause of the Dump Valve opening is presently under investigation.

1 F

$ ~

Forced Scheduled 2

Reason:

A:

Equipment Failure (Explain)

B:

Maintenance or Test C:

Refueling D:

Regulatory Restriction E:

Operator Training and License Examination F:

Administrative G:

Operational Error (Explain)

H:

Other (Explain) 3 Method:

1:

Manual 2:

Manual Scram 3:

Automatic Scram 4:

Other (Explain) 4Exhibit G Instructions for preparation of data entry sheets for Licensee Event Report (LER) File (NUREG 1061) 5Exhibit I:

Same Source

I

V DOCKET NO.:

UNIT'NAME:

COMPLETED BY:

TELEPHONE:

'ATE:

PAGE 50-316 D.C.

Cook Unit 2 R.

D. Reynnells (616) 465-5901 March 7, 1994 Page 1 of 1 MONTHLY OPERATING ACTIVITIES FEBRUARY 1994 HIGHLIGHTS The unit entered the reporting period in Mode 1 at 75% RTP.

The unit exited this reporting period in Mode 3 at 04 RTP.

Reactor power was ramped down to 57< RTP on February 1,

1994 to conduct Main Feedpump Condenser tube inspections.

On February 21, 1994 the reactor tripped during post maintenance testing of Steam Generator

¹4 Stop Valve Dump Valve.

There were no challenges to the pressurizer safety valves or power operated relief valves.

Gross Electrical generation for the month of February was 343460 MWH.

DETAILS 02-01-94 02-02-94 02-04-94 1300 1444 2015 0135 1905 Commenced reactor power increase to 854 RTP to meet system demands.

Reactor power is at 854 RTP.

Commenced reactor power increase to 904 RTP to meet system demands.

Reactor power is at 904 RTP.

Commenced reactor power reduction to inspect the Main Feedpump condenser tubes.

02-05-94 02-06-94 0150 Reactor power is at 574 RTP.

1322 Commenced reactor power increase to 60% RTP.

02-21-94 1500 1413 Reactor power is at 604 RTP.

Reactor trip on LoLo level signal on ¹4 Steam Generator.

The RCS is in Mode 3.

~

~

8 li